基于MagicMC与COBRA的西安脉冲堆物理-热工耦合方法研究OA

To accurately obtain the neutronic and thermal-hydraulic parameters of Xi'an Pulsed Reactor(XAPR)under steady-state operation and enhance its safety analysis and operational prediction capabilities,a systematic study on a neutronic-thermal-hydraulics coupling method is conducted using the domestic Monte Carlo code MagicMC and the subchannel analysis code COBRA.The correctness of the MagicMC established in this paper is validated using experimental cold-critical rod position data from the Pulsed Reactor.By coupling the MagicMC and COBRA codes,the core neutronic-thermal-hydraulic coupling interface program,named XAPR-PTC,is developed.This program enables iterative exchange of key parameters between the two codes,including power distribution,heat source distribution,temperature,and density feedback for fuel and coolant.Using XAPR-PTC,coupled neutronic-thermal-hydraulics calculations are performed for the reactor operating at a steady state power level of 2 MW,yielding detailed distributions of core power and temperature fields.Comparisons of the simulation results for key core parameters,such as the maximum temperature at fuel center and maximum cladding temperature with experimental values,show relative deviations of 3.42％and 1.22％,respectively.These results confirm the accuracy and reliability of the developed coupling program.The research findings are expected to significantly improve the neutronics-thermal-hydraulics safety analysis capability for Xi'an Pulsed Reactor.